§ 50.36aTechnical specifications on effluents from nuclear power reactors.

(a) To keep releases of radioactive materials to unrestricted areas during normal conditions, including expected occurrences, as low as is reasonably achievable, each licensee of a nuclear power reactor and each applicant for a design certification or a manufacturing license will include technical specifications that, in addition to requiring compliance with applicable provisions of § 20.1301 of this chapter, require that:

(1) Operating procedures developed pursuant to § 50.34a(c) for the control of effluents be established and followed and that the radioactive waste system, pursuant to § 50.34a, be maintained and used. The licensee shall retain the operating procedures in effect as a record until the Commission terminates the license and shall retain each superseded revision of the procedures for 3 years from the date it was superseded.

(2) Each holder of an operating license, and each holder of a combined license after the Commission has made the finding under § 52.103(g) of this chapter, shall submit a report to the Commission annually that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous 12 months, including any other information as may be required by the Commission to estimate maximum potential annual radiation doses to the public resulting from effluent releases. The report must be submitted as specified in § 50.4, and the time between submission of the reports must be no longer than 12 months. If quantities of radioactive materials released during the reporting period are significantly above design objectives, the report must cover this specifically. On the basis of these reports and any additional information the Commission may obtain from the licensee or others, the Commission may require the licensee to take action as the Commission deems appropriate.

(b) In establishing and implementing the operating procedures described in paragraph (a) of this section, the licensee shall be guided by the following considerations: Experience with the design, construction, and operation of nuclear power reactors indicates that compliance with the technical specifications described in this section will keep average annual releases of radioactive material in effluents and their resultant committed effective dose equivalents at small percentages of the dose limits specified in § 20.1301 and in the license. At the same time, the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power even under unusual conditions which may temporarily result in releases higher than such small percentages, but still within the limits specified in § 20.1301 of this chapter and in the license. It is expected that in using this flexibility under unusual conditions, the licensee will exert its best efforts to keep levels of radioactive material in effluents as low as is reasonably achievable. The guides set out in appendix I, provide numerical guidance on limiting conditions for operation for light-water cooled nuclear power reactors to meet the requirement that radioactive materials in effluents released to unrestricted areas be kept as low as is reasonably achievable.

Submit comments by September 1, 2015. Comments received after this date will be considered if it is practical to do so, but the NRC is only able to ensure consideration of comments received on or before this date.

10 CFR Part 50, Appendix I

Summary

The U.S. Nuclear Regulatory Commission (NRC) is issuing this advance notice of proposed rulemaking (ANPR) to obtain input from stakeholders on the development of a regulatory basis for the NRC's regulations governing radioactive effluents from nuclear power plants. The regulatory basis would support potential changes to better align the NRC regulations governing dose assessments for radioactive effluents from nuclear power plant operations with the most recent terminology and dose-related methodology published by the International Commission on Radiological Protection (ICRP) contained in the ICRP Publication 103 (2007). The NRC has identified specific questions and issues with respect to a possible revision of the NRC's current regulations and guidance governing radioactive gaseous and liquid effluents from nuclear power plants. The NRC seeks public and other stakeholder input on these questions and issues in order to develop the regulatory basis.

Submit comments by July 6, 2015. Comments received after this date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this date. Although a time limit is given, comments and suggestions in connection with items for inclusion in guides currently being developed or improvements in all published guides are encouraged at any time.

10 CFR Parts 50 and 52

Summary

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1322, “Alternate Risk-Informed Approach for Addressing the Effects of Debris On Post-Accident Long-Term Core Cooling.” This DG proposes new guidance that describes methods and procedures that the NRC staff considers acceptable for complying with a voluntary, risk-informed alternative in a proposed revision of the NRC's regulation governing the design of emergency core cooling systems (ECCS).

The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking from Michael D. Tschiltz, on behalf of the Nuclear Energy Institute (NEI or the petitioner), dated January 15, 2015, requesting that the NRC clarify the applicability of an NRC regulation to combined licenses (COLs). The NRC regulation allows structures, systems, and components (SSCs) of nuclear power reactors to be re-categorized based upon risk-informed considerations. Such re-categorization would result in changes in which NRC requirements would apply to those SSCs. The petition was docketed by the NRC on February 6, 2015, and has been assigned Docket No. PRM-50-110. The NRC is not requesting public comment on PRM-50-110 at this time.

The docket for the petition for rulemaking, PRM-50-107, is closed on March 17, 2015.

10 CFR Parts 30, 40, 50, 52, 60, 61, 63, 70, 71, and 72

Summary

The U.S. Nuclear Regulatory Commission (NRC) will consider in the rulemaking process the issues raised in a petition for rulemaking (PRM), PRM-50-107, submitted by James Lieberman (the petitioner). The petitioner requested that the NRC amend its regulations to require that all persons seeking NRC approvals provide the NRC with complete and accurate information. Current NRC regulations pertaining to completeness and accuracy of information apply only to NRC licensees and license applicants. The NRC has determined that the issues raised in the PRM have merit and are appropriate for consideration in the rulemaking process.

Petition for rulemaking; notice of docketing, and request for comment.

Submit comments by March 30, 2015. Comments received after this date will be considered if it is practical to do so, but the NRC is able to assure consideration only for comments received on or before this date.

10 CFR Part 50

Summary

The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking (PRM) from Sandra Gavutis on behalf of C-10 Research and Education Foundation (C-10 or the petitioner), dated September 25, 2014, requesting that the NRC amend its regulations to provide improved identification techniques against Alkali-Silica Reaction (ASR) concrete degradation at nuclear power plants. The petition was docketed by the NRC on October 8, 2014, and has been assigned Docket No. PRM-50-109. The NRC is requesting public comments on this petition for rulemaking.